title: solid waste activity calculation from ap1000 pdfs...page 4 of 31 1 purpose of calculation 2 3...
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Forms/NS-NPP/DocumentCoverSheet-f3-4-1-1.doc
F-3.4.1-1 Rev 3
DOCUMENT COVER SHEET TDC: Permanent File:
DOCUMENT NO. REVISION PAGE ASSIGNED TO OPEN ITEMS (Y/N)
UKP-GW-GL-003 0 1 of 34 W-Russ N
DOCUMENT STATUS: PRE CFC CAE DES Westinghouse Acceptance of AP1000 Design Partner Document by:
Electronically Approved (Name and Date)
ALTERNATE DOCUMENT NUMBER: N/A
ORIGINATING ORGANIZATION: NPP / NSE I
WORK BREAKDOWN #: N/A
TITLE: Solid Waste Activity Calculation from AP1000
ATTACHMENTS:
N/A
CALCULATION/ANALYSIS REFERENCE:
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DCP/DCA/EDCR # INCORPORATED IN THIS DOCUMENT REVISION:
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ELECTRONIC FILENAME
UKP-GW-GL-003
ELECTRONIC FILE FORMAT
ELECTRONIC FILE DESCRIPTION
© 2010 WESTINGHOUSE ELECTRIC COMPANY LLC, ALL RIGHTS RESERVED – WESTINGHOUSE NON-PROPRIETARY CLASS 3
All Class 3 Documents require the following two approvals in lieu of a Form 36.
LEGAL REVIEW L. A. Campagna
SIGNATURE / DATE (If processing electronic approval select option)
Electronically Approved***
PATENT REVIEW D. E. Ekeroth
SIGNATURE / DATE Electronically Approved***
© 2010 WESTINGHOUSE ELECTRIC COMPANY LLC, ALL RIGHTS RESERVED – WESTINGHOUSE PROPRIETARY CLASS 2
This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or its subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in strict accordance with the terms and conditions of the agreement under which it was provided to you.
© 2010 WESTINGHOUSE ELECTRIC COMPANY LLC, ALL RIGHTS RESERVED and/or STONE & WEBSTER, INC.
WESTINGHOUSE PROPRIETARY CLASS 2 and/or STONE & WEBSTER CONFIDENTIAL AND PROPRIETARY
This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or is the property of and contains Confidential and Proprietary Information owned by Stone & Webster, Inc. and/or their affiliates, subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in strict accordance with the terms and conditions of the agreement under which it was provided to you.Third Party Provided Information To be used only for the specific contract under which it was provided. Requirements and responsibilities for this information are specified in APP-GW-GAP-104.
ORIGINATOR(S) WEC 6.1.pdf Larry R. Eisenstatt
SIGNATURE / DATE (If processing electronic approval select option) Electronically Approved***
REVIEWER(S) WEC 6.1.pdf Dennis M. Popp
SIGNATURE / DATE Electronically Approved***
SIGNATURE / DATE
SIGNATURE / DATE
Verification Method: Independent Review VERIFIER(S) WEC 6.1.pdf Ronald P. Vijuk
SIGNATURE / DATE Electronically Approved***
Plant Applicability: All AP1000 plants except: Only the following plants: UKP
APPLICABILITY REVIEWER WEC 6.1.pdf
J. A. Speer SIGNATURE / DATE Electronically Approved***
RESPONSIBLE MANAGER* WEC 6.1.pdf
Paul A. Russ
SIGNATURE / DATE
Electronically Approved***
* Approval of the responsible manager signifies that the document and all required reviews are complete, the appropriate proprietary class has been assigned, electronic file has been provided to the EDMS, and the document is released for use.
*** Electronically approved records are authenticated in the electronic document management system. When a document is approved, this footnote is replaced by a footnote with a date stamp.
Westinghouse Non-Proprietary Class 3
Westinghouse Electric Company LLC
P.O. Box 355 Pittsburgh, PA 15230
Copyright © 2010 Westinghouse Electric Company LLC
All Rights Reserved
Solid Waste Activity Calculation from AP1000
UKP-GW-GL-003, Revision 0
Revision History Solid Waste Activity Calculation from AP1000
Westinghouse Electric Company LLC
P.O. Box 355 Pittsburgh, PA 15230
Copyright © 2010 Westinghouse Electric Company LLC
All Rights Reserved
REVISION HISTORY
Revision Description of Changes
0 Initial Submittal
Solid Waste Activity Calculation from AP1000 Doc No: 63000333-000-000-111-C-0014Rev:2
Page 2 of 31
Revision Description of Change
1 First Issue. The calculation includes the activity fingerprint for General LLW, and supersedes 63000333-000-000- 111-C-0010 (UKP-GW-GL-013) and 63000333-000-000- 111-C-0013, the activity fingerprints for CPS Resin and Waste Oil respectively
2 Updated to include activity fingerprint for Steam Generator Sludge. This now supersedes63000333-000-000-111-C-0012
REVISION SUMMARY
©Aker Solutions E & C Ltd. This document and the information contained herein is commercially confidential and is the property and copyright of Aker Solutions E&C Ltd. It must not be disclosed to any third party without prior written consent of Aker Solutions E&C Ltd.
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Page 3 of 31
1
2 Glossary
3
4 CfA Conditions for Acceptance5 CPS Condensate Polishing System
6 DCD Design Control Document
7 ILW Intemediate level Waste
8 LLW Low level Waste
9 LLWR Low level Waste Repository10 SGBD Steam Generator Blowdown
11
12
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14 Bq Becquerel
15 Ci Curie
16 Te Tonne
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50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
Project Number:
63000333 111 C 0014
Area: System: Discip. Code: Rev:
Status:
2
S1
Doc. Type:
Sequen. Number:
000 000
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Page 4 of 31
1 Purpose of Calculation
2
3 As part of the Generic Design Assessment (GDA) for the Westinghouse AP1000 nuclear power station, it is necessary to demonstrate4 that all waste produced from the operation, maintenance and decommissioning of such a plant will be disposable. This process has5 included obtaining acceptance in principle from the Low Level Waste Repository (LLWR).6
7 The purpose of this calculation is to determine the activity of the following Low Level Waste (LLW) streams;
8 1. General LLW
9 2. Condensate Polishing Resin
10 3. Waste Oil11 4. Steam Generator Sludge
12
13 This calculation will determine the concentration of the isotopes present in each of the waste streams and will also determine the final
14 weight and volume of the waste package to be disposed of.
15
16 The activities of the following isotopes are specifically required to show that the waste will be disposable at the Low Level Waste17 Repository (LLWR); 18
19 Uranium
20 Ra-226
21 Th-232
22 Other alpha
23 C-14
24 I-129
25 H-3
26 Co-60
27 Other radionuclides
28
29 Introduction
30
31 General LLW32 The general LLW that will arise is expected to consist of a range of slightly contaminated materials. This will include; Plastics; Paper;
33 Incinerator ash; Metallic Items; Clothing; Rubber; Filters; Redundant Equipment; Glass; Wood.
34 The rates of arising for different materials will vary through the cycle. Individual drums will not be representative of the stream
35 averages. No large items that may require special handling are expected to arise routinely.
36
37 Condensate Polishing Resin38 The Condensate Polishing System (CPS) is used to remove corrosion products and ionic impurities from the condensate39 system during plant startup, hot standby, power operation with abnormal secondary cycle chemistry, safe shutdown, and cold40 shutdown operations.41
42 The CPS resin can become contaminated with radionuclides if there is leakage from the primary circuit to the secondary circuit.43 Therefore the only radionuclides that will be present on the CPS resin are those present in the primary cooling circuit. 44
45 Although the radionuclides will decay over time and hence the activity will decrease, activities will initially be calculated without 46 taking this decay into account. This will provide a conservative case in terms of the activity on the CPS resin. 47
48 Waste Oil49 Waste radioactive oil arises from motor pumps in the chemical and volume control system. Waste oil may also arise from spills and leaks50 from gear boxes or other sources.
000 000
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Sequen. Number:Project Number:
63000333 111 C 0014
Discip. Code: Rev:
Status:
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©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
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000 000
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63000333 111 C 0014
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1 The oil is a standard commerically available lubricating oil that is normally expected to be non-radioactive.The volumes and activities2 stated are based on very conservative estimates. The oil will become contaiminated with radioactivity if there is a pump seal leak3 or other such failure in the equipment. As a result of this the activity it is expected to have will be similar to the activity that would be4 expected to arise from a primary to secondary circuit leakage i.e. similar to reactor coolant. 5
6 Steam Generator Sludge7 The steam generators produce steam from the secondary side water system to drive the steam turbines. This process of generating 8 steam can cause a buildup of sludge on the tubes within the steam generators. The material may be corrosion products 9 containing magnetite usually non-radioactive. Also impurities from makeup water and possibly from condenser tube leaks that build 10 up over the cycle.This sludge is periodically removed to prevent it casuing problems with heat transfer and corrosion of the tubes within11 the steam generators. 12
13 Assumptions
14 The following assumptions have been made during this calculation;
15 1 General LLW will have the same activity as that produced from Sizewell B16 2 The CPS resin has an operating time of 30 days within an 18 month cycle (Ref 1)
17 3 0.25% Fuel defects (Ref 7)
18 4 Fission gases have been excluded as they don't hold up on the Ion Exchange Resin
19 5 There is a 90 day storage period in the CPS resin tank during which the radionuclides will decay prior to conditioning (Ref 1)
20 6 All primary to secondary circuit leakage activity is recovered on the CPS Ion Exchange resin
21 7 No allowance has been made for the activity removed by the Steam Generator Blowdown (SGBD) System
22 8 Primary to secondary circuit leakage will last no longer than 30 days
23 9 Realistic primary circuit activities are used as defined in tables 11.1-7 and 11.1-8 of the European DCD
24 10 Resin:cement ratio is 50:50 (Ref 11)
25 11 Density of cement mixture is 2.4 Te/m3 (Ref 12)
26 12 A total of 1m3 of waste radioactive oil will be generated over the lifetime of the plant (includes 0.088m3 for spillages)(Ref 10)27 13 The activity of the oil is based on 0.15% of the rector coolant activity(Ref 14)
28 14 The oil is based on OMV ECO TRUCK SAE 10W-40 with density of 869kg/m3 at 20C
29 15 Decay of radionuclides has not been taken into account w.r.t. waste oil
30 16 The sludge has the same activity as the secondary side coolant
31 17 The sludge has the same density as the secondary side coolant
32 18 The activity in the sludge will decay for at least 30 days prior to disposal
33 19 Secondary circuit activities are used as defined in table 11.1-5 of the European DCD (Ref 19)
34 20 Secondary side density is assumed to be that of water
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The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
©Aker Solutions E & C Ltd.
EDT 009 0808
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000 000
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Sequen. Number:Project Number:
63000333 111 C 0014
Discip. Code: Rev:
Status:
Area: System:
1 Results2 The Total activity triggers for the LLWR have been taken from Reference 13 and are outlined below; 3 Uranium = MBq4 Ra-226 & Th-232 = MBq5 Other Alpha = MBq6 C-14 = MBq7 I-129 = MBq8 H-3 = MBq9 Co-60 = MBq10 Other radionuclides = MBq Note 111
12 Note 1: This Also includes the Co-60 Activity13 The calculation of the values outlined below can be found on pages 10 to 30 of this calculation. 14
15 General LLW
16 The volume of general LLW to be disposed of per year from original estimate was = m3
17 The total weight of this volume of waste was = Te
18
19 The total activity concentrations of the relevent Istopes are;
20
21 Uranium = MBq
22 Ra-226 = MBq
23 Th-232 = MBq
24 Other alpha = MBq
25 C-14 = MBq
26 I-129 = MBq
27 H-3 = MBq
28 Co-60 = MBq
29 Other radionuclides = MBq
30
31 Comparing total activities of the istopes within the general LLW and the total activity triggers for the LLWR, it is evident that the activity
32 within the waste is much lower than the triggers for the repository and therefore it is expected that this waste will be acceptable by the
33 LLWR. Also given the large difference between the actual activity and the triggers it is not expected that changes to the overall waste volumes
34 affect the activity within the waste significantly enough to prevent it being accepted by the LLWR. This is demonstrated by the results
35 below which show the activities using the increased volume of waste;
36
37 The volume of general LLW to be disposed of per year from improved estimate is = m3
38 The total weight of this volume of waste is = Te
39
40 Uranium = MBq
41 Ra-226 = MBq
42 Th-232 = MBq
43 Other alpha = MBq
44 C-14 = MBq
45 I-129 = MBq
46 H-3 = MBq
47 Co-60 = MBq
48 Other radionuclides = MBq
49
50 As can be seen this increase in activity is not significant and therefore it is expected that this waste will meet the LLWR CfA.
0.000.33
0.000.00
The information on this sheet may be used only for the purpose
0.000.00
0.29
0.320.000.17
14.01
0.1512.65
©Aker Solutions E & C Ltd.
to third parties. This sheet and all copies must be returned on demand.for which it is supplied by the Company and must not be shown
214.19
0.00
0.000.37
237.18
25.9551.9
46.923.44
900009000
900001500015000
3000000600000
4500000
EDT 009 0808
Page 7 of 31
000 000
2
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Sequen. Number:Project Number:
63000333 111 C 0014
Discip. Code: Rev:
Status:
Area: System:
1 Condensate Polishing Resin2
3 The total conditioned volume of the waste to be disposed of is m3
4 The total weight of the waste (encapsulated) to be disposed of is kg
5
6 Prior to accounting for decay during the 90day hold up period within the CPS resin tank the total activity on the CPS resin is7 GBq / Te.
8 After accounting for the decay of the radionuclides during the 90 hold up period within the CPS resin tank the total activity of the CPS 9 resin is GBq / Te.
10
11 The total activity concentrations of the relevent Istopes are;
12 Expected Maximum13 Uranium = MBq
14 Ra-226 = MBq
15 Th-232 = MBq
16 Other alpha = MBq
17 C-14 = MBq
18 I-129 = MBq
19 H-3 = MBq
20 Co-60 = MBq
21 Other radionuclides = MBq
22
23 The activity concentrations of the individual isotopes stated above do not include decay to give worst case and have been taken 24 from table 6.25 From experience it is not expected that a primary to secondary leak would not last longer than 7 days, therefore the expected
26 values are based on the activity after a 7 day leakage and the maximum values are based on the activity after a 30 day leakage
27
28 Comparing total activities of the istopes within the CPS resin and the total activity triggers for the LLWR, it is evident that the total
29 activity within the waste is lower than the triggers for the repository and therefore it is expected that this waste will be acceptable
30 by the LLWR.
31
32 Waste Oil
33
34 The volume of waste oil to be disposed of per year will be = 1 m3
35
36 The total weight of this volume of waste will be = Te
37
38 The total activity concentrations of the relevent isotopes are;
39
40 Uranium = MBq
41 Ra-226 = MBq
42 Th-232 = MBq
43 Other alpha = MBq
44 C-14 = MBq
45 I-129 = MBq
46 H-3 = MBq
47 Co-60 = MBq
48 Other radionuclides = MBq
49
50
©Aker Solutions E & C Ltd.
for which it is supplied by the Company and must not be shown
23.92
The information on this sheet may be used only for the purpose
to third parties. This sheet and all copies must be returned on demand.
11.6018270
16.6
00
9.4
000
15357.4
000
037795.58819.0
65817.3
0.87
0.00E+000.00E+00
2.12E-028.40E+01
0.00E+000.00E+000.00E+000.00E+004.82E+01
000
3.88
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000 000
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63000333 111 C 0014
Discip. Code: Rev:
Status:
Area: System:
1 Comparing total activities of the istopes within the Waste Oil and the total activity triggers for the LLWR, it is evident that the activity 2 within the waste is much lower than the triggers for the repository and therefore it is expected that this waste will be acceptable by the
3 LLWR.
4
5 Steam Generator Sludge6
7 The volume of waste sluidge to be disposed of per year will be = m3
8
9 The total weight of this volume of waste will be = Te
10
11 The total activity concentrations of the relevent isotopes are;
12
13 Uranium = MBq
14 Ra-226 = MBq
15 Th-232 = MBq
16 Other alpha = MBq
17 C-14 = MBq
18 I-129 = MBq
19 H-3 = MBq
20 Co-60 = MBq
21 Other radionuclides = MBq
22
23 Comparing total activities of the istopes within the Waste Sludge and the total activity triggers for the LLWR, it is evident that the activity
24 within the waste is much lower than the triggers for the repository and therefore it is expected that this waste will be acceptable by the
25 LLWR.
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50©Aker Solutions E & C Ltd.
84.85
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
0.00E+000.00E+000.00E+000.00E+000.00E+007.53E-083.12E+031.15E-031.33E+01
0.09
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1
2 Conclusion
3
4 General LLW5
6 The total activity within the waste is much lower than the triggers for the LLWR and therefore it is expected that this waste will meet the
7 Conditions for Acceptance of the the LLWR.
8
9 Also given the large difference between the actual activity and the triggers it is not expected that changes to the overall waste volumes
10 affect the activity within the waste significantly enough to prevent it being accepted by the LLWR.
11
12 Condensate Polishing Resin
13
14 The upper limits for LLW are 4GBq/Te alpha emitters and 12GBq/Te Beta/gamma emitters (Ref 5). There are no alpha radiation emitters
15 present in this waste.
16 Given that the total activity on the CPS resin after the 90 day decay period is 9.4GBq/Te and the upper limit for LLW is 12GBq/Te,
17 it can be concluded from this conservative calculation that the spent CPS resin will be classified as LLW .
18
19 It is expected that the SGBD system will remove a certain proportion of the activity thus can be expected that the actual activity of the
20 CPS resin will be lower than that calculated.
21
22 Therefore it can be concluded based on this very conservative calculation that the CPS resin will be accpeted for disposal at the LLWR
23
24 It should be noted that a D1 form with the data determined in this calculation has been accepted by the LLWR. The D1 form accepted by
25 the LLWR contains two errors;
26 1 Expected Co-60 activity stated as 0.08819 MBq 27 2 Expected other activity stated as 15357.3 Mbq28
29 Neither of these errors affect the conclusions of this calculation as the actual calculated values are still within the acceptance criteria30 for disposal at the LLWR.
31
32 The total activity within the waste is much lower than the triggers for the LLWR and therefore it is expected that this waste will meet the
33 Conditions for acceptance of the the LLWR.
34
35 Waste Oil
36
37 Comparing total activities of the istopes within the waste oil and the total activity triggers for the LLWR, it is evident that the activity
38 within the waste is much lower than the triggers for the repository and therefore it is expected that this waste will be acceptable by the
39 LLWR.
40
41 Steam Generator Sludge42
43 Comparing total activities of the istopes within the Waste Sludge and the total activity triggers for the LLWR, it is evident that the activity
44 within the waste is much lower than the triggers for the repository and therefore it is expected that this waste will be acceptable by the
45 LLWR.
46
47
48
49
50
for which it is supplied by the Company and must not be shownThe information on this sheet may be used only for the purpose
©Aker Solutions E & C Ltd.
to third parties. This sheet and all copies must be returned on demand.
EDT 009 0808
Page 10 of 31
1 General LLW
2
3 Source Information
4 Volume of Waste per year = 46.87 m3 Note 2
5 Bulk Density of General LLW = 0.5 Te/m3 Ref 16
6 The following data on the Isotopes and their respective activities have been reproduced from Ref 16 (Assumption 1)
7
8
9
10
11 H 3 12 C 1413 Mn 54 14 Fe 55 15 Co 60 16 Ni 63 17 Zn 65 18 Sr 90 19 Ru 106 20 Ag 108m 21 Ag 110m 22 Sb 125 23 Cs 134 24 Cs 137 25 Ce 144 26 Pm 147 27 Pu 238 28 Pu 239 29 Pu 240 30 Pu 241 31 Am 241 32 Cm 242 33 Cm 243 34 Cm 244 35 Other β / γ 36 Table 1: SZB Isotope Activity37
38 Note 2: This volume has been taken from an earlier version of the process mass balance (Ref 17). See Note 3 for 39 further details. 40
41 Calculation Method42
43 Using the assumed volume of waste per year the activity values can be converted to MBq as follows;
44
45 Activity (MBq) = SZB Activity x Assumed volume x 1000000
46
47 Taking Tritium (H-3) as an example;
48
49 Activity of H-3 (MBq) = 3.3E-09 x 46.87 x 1000000 = 1.5E-0150
4.70E-102.40E-101.60E-101.07E-06
1.50E-091.40E-091.80E-072.70E-09
4.30E-081.60E-092.70E-086.30E-10
3.20E-093.70E-102.10E-098.50E-09
2.00E-073.20E-092.10E-089.90E-09
SZB Isotpe Activity (TBq/m3)Nuclide
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
000
Area : System:
to third parties. This sheet and all copies must be returned on demand.
3.30E-096.10E-091.30E-072.60E-062.70E-07
2
Status: S1
Rev.
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
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Area : System: 2
Status: S1
Rev.
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
1
2 The results for all the relevent Isotopes are Shown in Table 2 Below
3
4
5
6
7 H 3 8 C 149 Mn 54 10 Fe 55 11 Co 60 12 Ni 63 13 Zn 65 14 Sr 90 15 Ru 106 16 Ag 108m 17 Ag 110m 18 Sb 125 19 Cs 134 20 Cs 137 21 Ce 144 22 Pm 147 23 Pu 238 24 Pu 239 25 Pu 240 26 Pu 241 27 Am 241 28 Cm 242 29 Cm 243 30 Cm 244 31 Other β / γ 32 Table 2: General LLW Activity
33
34 To determine the activity of the specific Isotopes required, the above Isotopes must be categorised as Alpha ( α), Beta (β) or
35 Gamma (γ) emitters. This has been done from Ref 6 and is shown in Table 3
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50
7.5E-035.0E+01
8.4E+001.3E-012.2E-021.1E-02
1.3E+003.0E-02
6.6E-02
4.6E-011.5E-011.7E-02
7.0E-02
9.8E-024.0E-012.0E+007.5E-02
1.07E-06
Activity (MBq)
1.5E-012.9E-016.1E+001.2E+021.3E+019.4E+001.5E-019.8E-01
2.70E-094.70E-102.40E-101.60E-10
6.30E-101.50E-091.40E-091.80E-07
8.50E-094.30E-081.60E-092.70E-08
9.90E-093.20E-093.70E-102.10E-09
2.70E-072.00E-073.20E-092.10E-08
Nuclide SZB Isotpe Activity (TBq/m3)
3.30E-09
2.60E-06
6.10E-091.30E-07
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
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000
Area : System: 2
Status: S1
Rev.
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
1
2
3
4
5
6
7 H 3 8 C 149 Mn 54 10 Fe 55 11 Co 60 12 Ni 63 13 Zn 65 14 Sr 90 15 Ru 106 16 Ag 108m 17 Ag 110m 18 Sb 125 19 Cs 134 20 Cs 137 21 Ce 144 22 Pm 147 23 Pu 238 24 Pu 239 25 Pu 240 26 Pu 241 27 Am 241 28 Cm 242 29 Cm 243 30 Cm 244 31 Other β / γ32 Total
33 Table 3: Decay Mode of Radionuclides
34 The activity of the specific Isotopes required are taken from table 3 above. These are outlined below;
35
36 Uranium 0.00E+00 MBq
37 Ra-226 0.00E+00 MBq
38 Th-232 0.00E+00 MBq
39 Other alpha 3.33E-01 MBq
40 C-14 2.86E-01 MBq
41 I-129 0.00E+00 MBq
42 H-3 1.55E-01 MBq
43 Co-60 1.27E+01 MBq
44 Other radionuclides 2.14E+02 MBq
45
46
47
48
49
50
4.59E-06 2.1E+02
β decay is 99.998% of the decay
α decay is 99.71% of the decay
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
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β- ααα
γ + β- γ + β- γ + β- β-
2.60E-06 1.2E+02
2.70E-07 1.3E+01
2.00E-07 9.4E+00
3.20E-09 1.5E-01
2.10E-08 9.8E-01
9.90E-09 4.6E-01
3.20E-09 1.5E-01
3.70E-10 1.7E-02
2.10E-09 9.8E-02
8.50E-09 4.0E-01
4.30E-08 2.0E+00
1.60E-09 7.5E-02
2.70E-08 1.3E+00
6.30E-10 3.0E-02
1.50E-09 7.0E-02
1.40E-09 6.6E-02
1.80E-07 8.4E+00
2.70E-09 1.3E-01
4.70E-10 2.2E-02
2.40E-10 1.1E-02
1.60E-10 7.5E-03
1.07E-06 5.0E+01
β- β-
γ + β+γ + β-
ECγ + β- β-
γ +β+
γ + β+
3.30E-09 1.5E-01
6.10E-09 2.9E-01
1.30E-07 6.1E+00
Nuclide SZB Isotpe Activity (TBq/m3) Activity (MBq)
αβ / γ
Remarks
α + β- αα
α + γ
Decay Mode (α, β or γ)
β- β-
EDT 009 0808
Page 13 of 31
000
Area : System: 2
Status: S1
Rev.
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
1
2 After the D1 form was issued to the LLWR, improved estimates for the waste volumes where obtained.
3
4 Volume of general LLW per year = 51.9 m3 Note 3
5
6 Using this improved volume of waste, the activity values from Table 1, and the calculation method outlined above, the
7 Following results for the fingerprint of the waste are obtained. These are outlined in Table 4.
8
9
10
11
12 H 3 13 C 1414 Mn 54 15 Fe 55 16 Co 60 17 Ni 63 18 Zn 65 19 Sr 90 20 Ru 106 21 Ag 108m 22 Ag 110m 23 Sb 125 24 Cs 134 25 Cs 137 26 Ce 144 27 Pm 147 28 Pu 238 29 Pu 239 30 Pu 240 31 Pu 241 32 Am 241 33 Cm 242 34 Cm 243 35 Cm 244 36 Other b/g 37 Total
38 Table 4: Revised Activity of General LLW
39
40
41 Uranium 0.00E+00 MBq42 Ra-226 0.00E+00 MBq43 Th-232 0.00E+00 MBq44 Other alpha 3.68E-01 MBq45 C-14 3.17E-01 MBq46 I-129 0.00E+00 MBq47 H-3 1.71E-01 MBq48 Co-60 1.40E+01 MBq49 Other radionuclides 2.37E+02 MBq50
4.59E-06 2.4E+021.07E-06 5.6E+01
2.40E-10 1.2E-02
1.40E-09 7.3E-02
1.80E-07 9.3E+00
6.30E-10 3.3E-02
1.60E-10 8.3E-03
2.70E-09 1.4E-01
4.70E-10 2.4E-02
4.30E-08 2.2E+00
1.50E-09 7.8E-02
1.60E-09 8.3E-02
2.70E-08 1.4E+00
2.10E-09 1.1E-01
8.50E-09 4.4E-01
3.20E-09 1.7E-01
3.70E-10 1.9E-02
2.10E-08 1.1E+00
9.90E-09 5.1E-01
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purpose
1.30E-07 6.7E+00
2.60E-06 1.3E+02
2.70E-07 1.4E+01
1.7E-01
6.10E-09 3.2E-01
for which it is supplied by the Company and must not be shownto third parties. This sheet and all copies must be returned on demand.
2.00E-07 1.0E+01
3.20E-09 1.7E-01
Nuclide SZB Isotpe Activity (TBq/m3) Activity (MBq)
3.30E-09
EDT 009 0808
Page 14 of 31
000
Area : System: 2
Status: S1
Rev.
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
1
2 Note 3: This information has been taken from Table 32 of Ref 17, excluding the volume of CPS resin. It is worth noting that
3 these volumes (and those of the intial estimates) are the conditioned volumes of waste and hence some have a compaction 4 factor applied to them. See Ref 17 for more details5
6
7 Final waste package
8
9 Volume
10
11 The Assumed Volume of waste initially used = 46.87 m312
13 Revised Volume of Waste = 51.9 m3 Ref 10
14
15 N.B. It is the initially assumed volume of waste that appears on the D1 form i.e. 47m3
16
17 Weight
18
19 Bulk Density of waste = 0.5 Te/m3 Ref 16
20
21 Weight of waste in waste package = volume of waste in waste package x Density of waste
22
23 Weight of waste in waste package = 46.87 x 0.50
24 = 23.44 Te
25
26 N.B. Using the revised volume of waste this will give a total weight of 25.95 m3
27
28 As stated in Note 3 the estimated weights may not be strictly correct due to some of the waste being compacted and some of it not. However
29 these estimates are sufficient enough for this stage of the design process.
30
31
32
33
34
35
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
©Aker Solutions E & C Ltd.
EDT 009 0808
Page 15 of 31
1 Condensate Polishing Resin
2
3 Source Information
4 Bulk volume of CPS resin per 18 month cycle = 204 ft3 Ref 10
5 Primary to secondary leakage rate = 75 Ib/day Ref 2
6 Duration of primary to secondary leak at given rate (Assumed) = 30 days Ref 8
7 Bulk density of CPS resin = 0.75 Te/m3 Ref 4
8 Decay time 90 days Ref 1
9
10 The following data on the Isotopes and their respective activities within the primary coolant have been extrated from Ref 3
11
12
13
14
15 Br-84 Y-93
16 I-131 Zr-95
17 I-132 Nb-95
18 I-133 Mo-99
19 I-134 Tc-99m
20 I-135 Ru-103
21 Rb-88 Ru-106
22 Cs-134 Rh-103m
23 Cs-136 Rh-106
24 Cs-137 Ag-110m
25 H-3 Te-129m
26 Na-24 Te-129
27 Cr-51 Te-131m
28 Mn-54 Te-131
29 Fe-55 Te-132
30 Fe-59 Ba-137m
31 Co-58 Ba-140
32 Co-60 La-140
33 Zn-65 Ce-141
34 Sr-89 Ce-143
35 Sr-90 Ce-144
36 Sr-91 Pr-143
37 Y-90 Pr-144
38 Y-91m W-187
39 Y-91 Np-239
40 Table 5: Reactor Coolant Activity
41 Calculation Method42
43 Total leakage from primary to secondary = Primary to secondary leakage rate x CPS operation duration
44 = 2250.0 Ib
45 = 1021.5 kg
46
47 Volume of CPS resin per 18month cycle = 5.78 m3
48
49 N.B. 1Ib = 0.454Kg
50 1ft3 = 0.0283 m3
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
2
Status: S1
Rev.
000
Area : System:
4.60E-02
0.42
5.90E-037.40E-047.90E-03
1
2.60E-031.30E-031.00E-032.50E-043.90E-034.40E-044.30E-041.20E-04
0.020.040.250.14
0.280.24
5.10E-036.30E-037.50E-026.30E-037.50E-021.10E-031.60E-042.90E-02
4.30E-033.30E-042.40E-045.60E-03
Reactor Coolant Activity (μCi/g)
Reactor Coolant Activity (μCi/g)NuclideNuclide
1.00E-059.80E-041.20E-065.70E-044.40E-06
1.40E-039.70E-031.50E-037.40E-031.10E-022.30E-021.30E-042.60E-033.40E-033.00E-033.40E-032.30E-032.00E-03
EDT 009 0808
Page 16 of 31
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
2
Status: S1
Rev.
000
Area : System:
1
2 Initially neglecting the decay over 90 days the activity concentration of primary coolant that leaks into the secondary system can be
3 calculated by;
4
5 Activity = Reactor coolant activity x total leakage from primary to secondary
6
7 See table 6 for results
8
9 Table 6 shows a total activity of 103.613 GBq
10
11 The activity concentration can then be converted into an activity concentration per m 3 of CPS resin by;
12
13 Activity concentration per m3 = Total Activity / m3 of resin
14
15 See table 6 for results
16
17 Table 6 shows a total activity concentration/ m3 of CPS resin of 17.94 GBq / m3
18
19 This can be converted to GBq per tonne by dividing by the bulk density of the CP resin
20 Bulk Density of CP resin = 0.75 Te/m3
21 Therefore the total activity concentration of the CPS resin is 23.92 GBq / Te
22
23 The limits for LLW are 4GBq/te alpha emmitters and 12 GBq/te Beta/gamma emmitters Ref 5
24
25 The total activity concentration on the CPS resin is not within the limits for LLW.
26
27
28
29 Now considering the decay period of 90 days:30
31 The half lifes of the Isotopes were determined from Ref 6 and are shown in table 7.
32
33 The activity concentration on the CPS resin after 90days of decay can be calculated from the following;
34
35
36 Decayed Activity Concentration (Gbq/m3) = Undecayed Activity Concentration (Gbq/m3) x EXP
37
38 Where T = Decay time (days)
39 t1/2 = Half Life (days)
40
41 The decayed activity concentrations for all the isotopes are shown in Table 2.
42
43 The total decayed activity on the CPS resin is 7.02 GBq/m3
44
45 This can be converted to GBq per tonne by dividing by the bulk density of the CP resin
46
47 Therefore the total activity concentration of the CPS resin is 9.36 GBq / Te
48
49
50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
×−
21
)2(t
TLn
×−
21
)2(t
TLn
EDT 009 0808
Page 17 of 31
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
2
Status: S1
Rev.
000
Area : System:
1 Table 6 - Activity per m3 of CPS resin2
3
4
5
6 Br-84
7 I-131
8 I-132
9 I-133
10 I-134
11 I-135
12 Rb-88
13 Cs-134
14 Cs-136
15 Cs-137
16 H-3
17 Na-24
18 Cr-51
19 Mn-54
20 Fe-55
21 Fe-59
22 Co-58
23 Co-60
24 Zn-65
25 Sr-89
26 Sr-90
27 Sr-91
28 Y-90
29 Y-91m
30 Y-91
31 Y-93
32 Zr-95
33 Nb-95
34 Mo-99
35 Tc-99m
36 Ru-103
37 Ru-106
38 Rh-103m
39 Rh-106
40 Ag-110m
41 Te-129m
42 Te-129
43 Te-131m
44 Te-131
45 Te-132
46 Ba-137m
47 Ba-140
48 La-140
49 Ce-141
50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purpose
Nuclide Reactor Coolant Activity (μCi/g) Activity (Ci) Activity (GBq) Activity per m3
resin (GBq/m3)
2.00E-02 2.04E-02
for which it is supplied by the Company and must not be shownto third parties. This sheet and all copies must be returned on demand.
7.56E-01 1.31E-014.00E-02 4.09E-02 1.51E+00 2.62E-012.50E-01 2.55E-01 9.45E+00 1.64E+001.40E-01 1.43E-01 5.29E+00 9.16E-014.20E-01 4.29E-01 1.59E+01 2.75E+002.80E-01 2.86E-01 1.06E+01 1.83E+002.40E-01 2.45E-01 9.07E+00 1.57E+005.90E-03 6.03E-03 2.23E-01 3.86E-027.40E-04 7.56E-04 2.80E-02 4.84E-037.90E-03 8.07E-03 2.99E-01 5.17E-021.00E+00 1.02E+00 3.78E+01 6.54E+004.60E-02 4.70E-02 1.74E+00 3.01E-012.60E-03 2.66E-03 9.83E-02 1.70E-021.30E-03 1.33E-03 4.91E-02 8.51E-031.00E-03 1.02E-03 3.78E-02 6.54E-032.50E-04 2.55E-04 9.45E-03 1.64E-033.90E-03 3.98E-03 1.47E-01 2.55E-024.40E-04 4.49E-04 1.66E-02 2.88E-034.30E-04 4.39E-04 1.63E-02 2.81E-031.20E-04 1.23E-04 4.54E-03 7.85E-041.00E-05 1.02E-05 3.78E-04 6.54E-059.80E-04 1.00E-03 3.70E-02 6.41E-031.20E-06 1.23E-06 4.54E-05 7.85E-065.70E-04 5.82E-04 2.15E-02 3.73E-034.40E-06 4.49E-06 1.66E-04 2.88E-054.30E-03 4.39E-03 1.63E-01 2.81E-023.30E-04 3.37E-04 1.25E-02 2.16E-032.40E-04 2.45E-04 9.07E-03 1.57E-035.60E-03 5.72E-03 2.12E-01 3.66E-025.10E-03 5.21E-03 1.93E-01 3.34E-026.30E-03 6.44E-03 2.38E-01 4.12E-027.50E-02 7.66E-02 2.83E+00 4.91E-016.30E-03 6.44E-03 2.38E-01 4.12E-027.50E-02 7.66E-02 2.83E+00 4.91E-011.10E-03 1.12E-03 4.16E-02 7.20E-031.60E-04 1.63E-04 6.05E-03 1.05E-032.90E-02 2.96E-02 1.10E+00 1.90E-011.40E-03 1.43E-03 5.29E-02 9.16E-039.70E-03 9.91E-03 3.67E-01 6.35E-021.50E-03 1.53E-03 5.67E-02 9.81E-037.40E-03 7.56E-03 2.80E-01 4.84E-021.10E-02 1.12E-02 4.16E-01 7.20E-022.30E-02 2.35E-02 8.69E-01 1.50E-011.30E-04 1.33E-04 4.91E-03 8.51E-04
EDT 009 0808
Page 18 of 31
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
2
Status: S1
Rev.
000
Area : System:
1 Table 6 - Activity per m3 of CPS resin (continued)2
3
4
5 Ce-143
6 Ce-144
7 Pr-143
8 Pr-144
9 W-187
10 Np-239
11 Total
12
13
14
15 N.B. 1Ci = 37GBq = 3.7E+10Bq
16
17 From Ref 6 all the Isotopes outlined in Tabe 6 have either Beta or Gamma decay modes i.e. There is no isotope which exhibits
18 Alpha Decay
19
20 The activity of the specific Isotopes required are taken from table 6 above. These are outlined below;
21
22 Uranium MBq
23 Ra-226 MBq
24 Th-232 MBq
25 Other alpha MBq
26 C-14 MBq
27 I-129 MBq
28 H-3 MBq
29 Co-60 MBq
30 Other radionuclides MBq
31
32 It should be noted that the individual isotopes have been taken from the undecayed data to provide a worst case scenario. 33
34
35
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50
0.00E+000.00E+000.00E+003.78E+04
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
Nuclide Reactor Coolant Activity (μCi/g) Activity (Ci) Activity (GBq) Activity per m3
resin (GBq/m3)2.60E-03 2.66E-03 9.83E-02 1.70E-02
3.06E-03 1.13E-01 1.96E-023.40E-03 3.47E-03 1.29E-01 2.22E-023.00E-03
1.50E-023.40E-03 3.47E-03 1.29E-01 2.22E-022.30E-03 2.35E-03 8.69E-02
1.79E+012.00E-03 2.04E-03 7.56E-02 1.31E-022.74E+00 2.80E+00 1.04E+02
1.66E+016.58E+04
0.00E+000.00E+000.00E+00
EDT 009 0808
Page 19 of 31
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
2
Status: S1
Rev.
000
Area : System:
1 Table 7- Activity after 90 days decay
2
3
4
5
6 Br-84
7 I-131
8 I-132
9 I-133
10 I-134
11 I-135
12 Rb-88
13 Cs-134
14 Cs-136
15 Cs-137
16 H-3
17 Na-24
18 Cr-51
19 Mn-54
20 Fe-55
21 Fe-59
22 Co-58
23 Co-60
24 Zn-65
25 Sr-89
26 Sr-90
27 Sr-91
28 Y-90
29 Y-91m
30 Y-91
31 Y-93
32 Zr-95
33 Nb-95
34 Mo-99
35 Tc-99m
36 Ru-103
37 Ru-106
38 Rh-103m
39 Rh-106
40 Ag-110m
41 Te-129m
42 Te-129
43 Te-131m
44 Te-131
45 Te-132
46 Ba-137m
47 Ba-140
48 La-140
49 Ce-141
50
to third parties. This sheet and all copies must be returned on demand.
0.00E+00
5.49E-284
0.00E+002.62E-01 8.04E+00 1.12E-04 7.45E-05 3.72E-051.31E-01 2.21E-02 0.00E+00
0.00E+00
2.75E-2849.16E-01 8.67E-01 5.02E-32 3.35E-32 1.67E-321.64E+00 9.56E-02 8.24E-284
0.00E+00
0.00E+001.83E+00 2.74E-01 1.97E-99 1.31E-99 6.56E-1002.75E+00 3.65E-02 0.00E+00
2.76E-05
0.00E+003.86E-02 7.54E+02 3.55E-02 2.37E-02 1.18E-021.57E+00 1.23E-02 0.00E+00
4.30E+00
1.38E-055.17E-02 1.10E+04 5.14E-02 3.43E-02 1.71E-024.84E-03 1.31E+01 4.14E-05
1.19E-03
2.15E+003.01E-01 6.23E-01 1.03E-44 6.89E-45 3.44E-456.54E+00 4.51E+03 6.45E+00
4.10E-03
5.96E-048.51E-03 3.12E+02 6.97E-03 4.64E-03 2.32E-031.70E-02 2.77E+01 1.79E-03
7.05E-03
2.05E-031.64E-03 4.45E+01 4.03E-04 2.68E-04 1.34E-046.54E-03 9.96E+02 6.15E-03
1.45E-03
3.53E-032.88E-03 1.92E+03 2.79E-03 1.86E-03 9.29E-042.55E-02 7.09E+01 1.06E-02
4.34E-05
7.26E-047.85E-04 5.05E+01 2.28E-04 1.52E-04 7.61E-052.81E-03 2.44E+02 2.18E-03
3.62E-16
2.17E-056.41E-03 4.01E-01 1.93E-70 1.29E-70 6.44E-716.54E-05 1.05E+04 6.50E-05
6.61E-06
1.81E-163.73E-03 3.45E-02 0.00E+00 0.00E+00 0.00E+007.85E-06 2.67E+00 5.43E-16
5.43E-04
3.30E-062.81E-02 4.24E-01 3.77E-66 2.51E-66 1.26E-662.88E-05 5.85E+01 9.91E-06
3.44E-12
2.72E-041.57E-03 3.50E+01 2.64E-04 1.76E-04 8.80E-052.16E-03 6.40E+01 8.15E-04
5.61E-03
1.72E-123.34E-02 2.50E-01 2.15E-110 1.43E-110 7.17E-1113.66E-02 2.75E+00 5.15E-12
0.00E+00
2.80E-034.91E-01 3.74E+02 4.15E-01 2.77E-01 1.38E-014.12E-02 3.93E+01 8.41E-03
3.74E-03
0.00E+004.91E-01 3.45E-04 0.00E+00 0.00E+00 0.00E+004.12E-02 3.90E-02 0.00E+00
0.00E+00
1.87E-031.05E-03 3.36E+01 1.64E-04 1.09E-04 5.45E-057.20E-03 2.50E+02 5.61E-03
0.00E+00
0.00E+009.16E-03 1.25E+00 1.94E-24 1.29E-24 6.47E-251.90E-01 4.83E-02 0.00E+00
0.00E+00
0.00E+009.81E-03 3.20E+00 3.35E-11 2.24E-11 1.12E-116.35E-02 1.74E-02 0.00E+00
7.50E-18
0.00E+007.20E-02 1.28E+01 5.40E-04 3.60E-04 1.80E-044.84E-02 1.77E-03 0.00E+00
1.50E-01 1.68E+00 1.12E-17 3.75E-181.25E-04 8.32E-05
Nuclide Activity per m3
resin (GBq/m3)Half life (Days)
(Ref 6)
Decayed Activity (GBq/m3) Leakage
rate 75Ib/day
Decayed Activity (GBq/m3)
Leakage rate 50Ib/day
Decayed Activity (GBq/m3) Leakage rate 25Ib/day
8.51E-04 3.25E+01 4.16E-05
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
EDT 009 0808
Page 20 of 31
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
2
Status: S1
Rev.
000
Area : System:
1 Table 7 - Activity after 90 days decay (continued)
2
3
4
5
6
7 Ce-143
8 Ce-144
9 Pr-143
10 Pr-144
11 W-187
12 Np-239
13 Total
14
15
16
17 N.B. 1.1Ci = 37GBq = 3.7E+10Bq
18 2. The Ba-137m value in table 2 above is incorrect, because Ba-137m is actually in secular equilibrium with it's parent,
19 Cs-137, which is long lived in comparison to Ba-137m i.e. 30.1 yrs in comparsion to 2.5mins. This does not
20 affect the conclusions.
21
22
23
24
25
26
27
28
29
30
31
32
33
34
35
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
1.18E-221.19E-02
1.70E-02 1.38E+00 3.55E-22 2.37E-22
0.00E+00
5.96E-031.96E-02 1.36E+01 1.98E-04 1.32E-04 6.60E-052.22E-02 2.85E+02 1.79E-02
2.89E-14
0.00E+001.50E-02 9.88E-01 5.82E-30 3.88E-30 1.94E-302.22E-02 1.20E-02 0.00E+00
1.44E-141.31E-02
Nuclide Activity per m3
resin (GBq/m3)Half life (Days)
(Ref 6)
Decayed Activity (GBq/m3) Leakage
rate 75Ib/day
Decayed Activity (GBq/m3)
Leakage rate 50Ib/day
Decayed Activity (GBq/m3) Leakage rate 25Ib/day
1.79E+01 3.17E+04 7.02E+002.36E+00 4.33E-14
2.34E+004.68E+00
EDT 009 0808
Page 21 of 31
111 C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
0014000
2
Status: S1
Rev.
000
Area : System:
1
2 Final waste package
3 If the CPS resin does not meet the off-site incineration facilities conditions for acceptance it is intended to encapsulate the CPS
4 resin in a cement formulation in 200L drums which can then be sent for disposal to the LLWR.
5
6 Volume
7 The cement to resin ratio will be 50:50 as per the similar waste stream at Sizewell B Ref 11
8
9 Volume of resin to be encapsulated = 5.8 m3
10 Percentage of resin per waste package (by volume) = 50%
11
12 Total volume of waste package = Volume of resin / Percentage of resin per waste package
13
14 Total volume of waste package = 5.80 \ 50%
15 = 11.60 m3
16
17 Weight
18
19 Bulk Density of resin = 0.75 Te/m3 Ref 4
20 The density of cement = 2.4 Te/m3 Ref 12
21
22 Weight of resin in waste package = volume of resin in waste package x Density of resin
23 Weight of resin in waste package = 5.80 x 0.75
24 = 4.35 Te
25
26 Weight of cement in Waste package = Volume of cement in waste package x Density of cement
27 = 5.80 x 2.4
28 = 13.92 Te
29
30 Total weight of waste package = Weight of resin in waste package + weight of cement in waste package
31 = 4.35 + 13.92
32 = 18.27 Te per 18 month cycle
33 = 18270 Kg per 18 month cycle
34
35
36
37
38
39
4041
42
43
44
45
46
47
48
49
50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
EDT 009 0808
Page 22 of 31
1 Waste Oil
2
3 Source Information
4 Volume of oil per year = 1 m3 Ref 1
5 Density of oil = 0.869 Te/m3 assumed
6
7 The following data on the Isotopes and their respective activities within the primary coolant have been extracted from Ref 3
8
9
10
11
12 Br-84 Y-93
13 I-131 Zr-95
14 I-132 Nb-95
15 I-133 Mo-99
16 I-134 Tc-99m
17 I-135 Ru-103
18 Rb-88 Ru-106
19 Cs-134 Rh-103m
20 Cs-136 Rh-106
21 Cs-137 Ag-110m
22 H-3 Te-129m
23 Na-24 Te-129
24 Cr-51 Te-131m
25 Mn-54 Te-131
26 Fe-55 Te-132
27 Fe-59 Ba-137m
28 Co-58 Ba-140
29 Co-60 La-140
30 Zn-65 Ce-141
31 Sr-89 Ce-143
32 Sr-90 Ce-144
33 Sr-91 Pr-143
34 Y-90 Pr-144
35 Y-91m W-187
36 Y-91 Np-239
37
38
39 Table 8: Reactor Coolant activity
4041 Calculation Method42
43 The activity of the waste oil is assumed to be 0.15% of the activity of the reactor coolant. Thus the isotope activity shown in table 8
44 above are pro-rated as below
45
46 Isotopic activity in waste oil = isotopic activity in reactor coolant x 0.15%
47
48 The results are shown in table 9
49
50
for which it is supplied by the Company and must not be shownto third parties. This sheet and all copies must be returned on demand.
0.020.040.250.14
Rev.
111
2
Status: S1C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
000 000
Area : System:
0014
Reactor Coolant Activity (μCi/g)
Reactor Coolant Activity (μCi/g)NuclideNuclide
0.420.280.24
5.90E-037.40E-047.90E-03
14.60E-022.60E-031.30E-031.00E-032.50E-043.90E-034.40E-044.30E-041.20E-041.00E-059.80E-041.20E-065.70E-044.40E-06
4.30E-033.30E-042.40E-045.60E-035.10E-036.30E-037.50E-026.30E-037.50E-021.10E-031.60E-042.90E-021.40E-039.70E-031.50E-037.40E-031.10E-022.30E-021.30E-042.60E-033.40E-033.00E-033.40E-032.30E-032.00E-03
2.74E+00Total Activity
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purpose
EDT 009 0808
Page 23 of 31
Rev.
111
2
Status: S1C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
000 000
Area : System:
0014
1
2 This gives the activity in μCi/g
3
4 Mass of oil over lifetime of plant = volume of oil over lifetime of plant x Density of oil
5
6 Mass of oil over lifetime of plant = 1 x 0.869 = 0.869 Te
7 = 869000 g
8
9 This allows the production of a fingerprint for the waste oil, as shown in Table 9
10
11
12
13
14
15
16
17
18
19
20
21
22
23
24
25
26
27
28
29
30
31
32
33
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35
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
EDT 009 0808
Page 24 of 31
Rev.
111
2
Status: S1C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
000 000
Area : System:
0014
1 Table 9 - Activity of waste Oil
2
3
4
5
6 Br-84
7 I-131
8 I-132
9 I-133
10 I-134
11 I-135
12 Rb-88
13 Cs-134
14 Cs-136
15 Cs-137
16 H-3
17 Na-24
18 Cr-51
19 Mn-54
20 Fe-55
21 Fe-59
22 Co-58
23 Co-60
24 Zn-65
25 Sr-89
26 Sr-90
27 Sr-91
28 Y-90
29 Y-91m
30 Y-91
31 Y-93
32 Zr-95
33 Nb-95
34 Mo-99
35 Tc-99m
36 Ru-103
37 Ru-106
38 Rh-103m
39 Rh-106
40 Ag-110m
41 Te-129m
42 Te-129
43 Te-131m
44 Te-131
45 Te-132
46 Ba-137m
47 Ba-140
48 La-140
49 Ce-141
50
2.00E-024.00E-022.50E-011.40E-014.20E-012.80E-012.40E-015.90E-03
2.60E-031.30E-031.00E-03
7.40E-047.90E-031.00E+004.60E-02
2.50E-043.90E-034.40E-044.30E-041.20E-041.00E-059.80E-041.20E-065.70E-044.40E-064.30E-033.30E-042.40E-045.60E-035.10E-036.30E-037.50E-026.30E-037.50E-021.10E-031.60E-042.90E-021.40E-039.70E-031.50E-037.40E-031.10E-022.30E-021.30E-04
3.00E-056.00E-053.75E-042.10E-046.30E-044.20E-043.60E-048.85E-061.11E-061.19E-051.50E-036.90E-053.90E-061.95E-061.50E-063.75E-075.85E-066.60E-076.45E-071.80E-071.50E-081.47E-061.80E-098.55E-076.60E-096.45E-064.95E-073.60E-078.40E-067.65E-069.45E-061.13E-049.45E-06
1.46E-052.25E-061.11E-05
1.13E-041.65E-062.40E-074.35E-05
1.65E-053.45E-051.95E-07
2.61E+015.21E+013.26E+021.82E+025.47E+023.65E+02
2.10E-06
3.13E+027.69E+009.65E-011.03E+011.30E+036.00E+013.39E+001.69E+001.30E+003.26E-015.08E+005.74E-015.61E-011.56E-011.30E-021.28E+001.56E-037.43E-015.74E-035.61E+004.30E-013.13E-017.30E+006.65E+008.21E+009.78E+018.21E+009.78E+011.43E+002.09E-013.78E+011.82E+001.26E+011.96E+009.65E+001.43E+013.00E+011.69E-01
9.65E+051.93E+061.21E+076.75E+062.03E+071.35E+071.16E+072.85E+053.57E+043.81E+054.82E+072.22E+061.25E+056.27E+044.82E+041.21E+041.88E+052.12E+042.07E+045.79E+034.82E+024.73E+045.79E+012.75E+042.12E+022.07E+051.59E+041.16E+042.70E+052.46E+053.04E+053.62E+063.04E+053.62E+065.31E+047.72E+031.40E+066.75E+044.68E+057.23E+043.57E+055.31E+051.11E+066.27E+03
Waste oil Activity (μCi)
Waste Oil activity (Bq)
9.65E-01
Nuclide Reactor Coolant Activity
Waste oil activity (μCi/g)
1.93E+001.21E+016.75E+002.03E+011.35E+011.16E+012.85E-013.57E-023.81E-014.82E+012.22E+001.25E-016.27E-024.82E-021.21E-021.88E-012.12E-022.07E-025.79E-034.82E-044.73E-025.79E-052.75E-022.12E-042.07E-011.59E-021.16E-022.70E-012.46E-013.04E-013.62E+003.04E-013.62E+005.31E-027.72E-031.40E+00
6.27E-03
6.75E-024.68E-017.23E-023.57E-01
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
Waste Oil activity (MBq)
5.31E-011.11E+00
EDT 009 0808
Page 25 of 31
Rev.
111
2
Status: S1C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
000 000
Area : System:
0014
1 Table 9 - Activity of waste Oil (continued)
2
3
4
5 Ce-143
6 Ce-144
7 Pr-143
8 Pr-144
9 W-187
10 Np-239
11 Total
12
13
14
15 N.B. 1Ci = 37GBq = 3.7E+10Bq
16 The Ba-137m value in table 2 above is incorrect, because Ba-137m is actually in secular equilibrium with it's parent,
17 Cs-137, which is long lived in comparison to Ba-137m i.e. 30.1 yrs in comparsion to 2.5mins. This does not
18 affect the conclusions.
19
20
21 From Ref 6 all the Isotopes outlined in Table 9 have either Beta or Gamma decay modes i.e. There is no isotope which exhibits
22 Alpha Decay
23
24 The activity of the specific Isotopes required are taken from table 9 above. These are outlined below;
25 Uranium = MBq
26 Ra-226 = MBq
27 Th-232 = MBq
28 Other alpha = MBq
29 C-14 = MBq
30 I-129 = MBq
31 H-3 = MBq
32 Co-60 = MBq
33 Other radionuclides = MBq
34
35
36
37
38
39
40
41
42
43
44
45
46
47
48
49
50
4.82E+012.12E-028.40E+01
0.00E+000.00E+000.00E+000.00E+00
0.00E+000.00E+00
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
3.00E-03
Nuclide Reactor Coolant Activity (μCi/g)
2.60E-033.40E-03
Waste oil activity (μCi/g)
Waste oil Activity (μCi)
Waste Oil activity (Bq)
3.40E-03
3.39E+004.43E+003.91E+004.43E+00
1.25E+051.64E+05
3.57E+03
5.10E-063.45E-063.00E-06
4.50E-06
1.32E+08
1.45E+051.64E+051.11E+059.65E+04
3.00E+002.61E+00
2.74E+00 4.11E-03
2.30E-032.00E-03
3.90E-065.10E-06
1.25E-01
9.65E-021.32E+02
Waste Oil activity (MBq)
1.64E-011.45E-011.64E-011.11E-01
EDT 009 0808
Page 26 of 31
Rev.
111
2
Status: S1C
Project Number: Doc. Type:
Sequen. Number:
63000333
Discip. Code:
000 000
Area : System:
0014
1
2 Final waste package
3
4 Volume
5
6 The volume of Oil to be disposed of per year is = 1 m3 Ref 1
7
8
9
10 Weight
11
12 Bulk Density of Oil = 0.869 Te/m3 assumed
13
14 Weight of oil in waste package = volume of oil in waste package x Density of oil
15
16 Weight of Oil in package = 1.00 x 0.87
17 = 0.87 Te
18
19 Total weight of waste package = 0.87 Te
20
21 N.B. This weight does not include the weight of any conditioning matrix as the details of this are currently unknown
22
23
24
25
26
27
28
29
30
31
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33
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4041
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50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
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EDT 009 0808
Page 27 of 31
1
2 Steam Generator Sludge3
4 Source Information
5
6 The following data on the Isotopes and their activity within the secondary coolant have been extracted from Ref 197
8
9
10 Br-83 2.30E-05 Y-91m 1.80E-06
11 Br-84 4.00E-06 Y-91 2.30E-07
12 Br-85 4.90E-08 Y-92 4.90E-07
13 I-129 2.40E-11 Y-93 1.50E-07
14 I-130 1.40E-05 Zr-95 2.70E-07
15 I-131 1.10E-03 Nb-95 2.70E-07
16 I-132 7.30E-04 Mo-99 3.40E-04
17 I-133 1.80E-03 Tc-99m 3.20E-04
18 I-134 8.10E-05 Ru-103 2.30E-07
19 I-135 8.70E-04 Rh-103m 2.30E-07
20 Rb-88 2.30E-04 Rh-106 2.00E-10
21 Rb-89 8.90E-06 Ag-110m 6.70E-07
22 Cs-134 2.10E-03 Te-127m 1.30E-06
23 Cs-136 3.00E-03 Te-127 3.20E-07
24 Cs-137 1.50E-03 Te-129m 4.40E-06
25 Cs-138 9.50E-05 Te-129 3.80E-06
26 H-3 1.00E+00 Te-131m 1.00E-05
27 Cr-51 2.20E-06 Te-131 2.80E-06
28 Mn-54 1.10E-06 Te-132 1.30E-04
29 Mn-56 1.30E-04 Te-134 3.20E-06
30 Fe-55 8.40E-07 Ba-137m 1.40E-03
31 Fe-59 2.20E-07 Ba-140 1.70E-06
32 Co-58 3.20E-06 La-140 6.00E-07
33 Co-60 3.70E-07 Ce-141 2.60E-07
34 Sr-89 3.30E-06 Ce-143 2.20E-07
35 Sr-90 1.50E-07 Ce-144 1.90E-07
36 Sr-91 3.30E-06 Pr-143 2.50E-07
37 Sr-92 4.00E-07 Pr-144 1.90E-07
38 Y-90 2.70E-08
39
40
41 Table 10: Secondary Side Coolant Activity42 Volume of sludge per year = 0.085 m3 Ref 1043 Density of sludge = 998.20 kg/m3 Ref 1844 Decay time = 30 days (Assumed to be a minimum)45
46
47
48
49
50
Nuclide Activity (μCi/g) Nuclide Activity
(μCi/g)
Doc. Type:
Sequen. Number: 2
Status: S1111 C
Project Number:
0014
Rev.
63000333 000 000
Area : System: Discip. Code:
Total Activity 1.01
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
EDT 009 0808
Page 28 of 31
Doc. Type:
Sequen. Number: 2
Status: S1111 C
Project Number:
0014
Rev.
63000333 000 000
Area : System: Discip. Code:
1
2 Calculation method
3
4 Total activity in sludge prior to decay is = 1.01E+00 μCi/g
5
6 The half lifes of the Isotopes were determined from Ref 6 and are shown in table 11.
7
8 The activity concentration on the sludge after 30 days of decay can be calculated from the following;
9
10
11 Decayed Activity Concentration (μCi/g) = Undecayed Activity Concentration (μCi/g) x EXP
12
13 Where T = Decay time (days)
14 t1/2 = Half Life (days)
15
16 The decayed activity concentrations for all the isotopes are shown in Table 11.
17
18
19
20 Br-83 2.30E-05
21 Br-84 4.00E-06
22 Br-85 4.90E-08
23 I-129 2.40E-11
24 I-130 1.40E-05
25 I-131 1.10E-03
26 I-132 7.30E-04
27 I-133 1.80E-03
28 I-134 8.10E-05
29 I-135 8.70E-04
30 Rb-88 2.30E-04
31 Rb-89 8.90E-06
32 Cs-134 2.10E-03
33 Cs-136 3.00E-03
34 Cs-137 1.50E-03
35 Cs-138 9.50E-05
36 H-3 1.00E+00
37 Cr-51 2.20E-06
38 Mn-54 1.10E-06
39 Mn-56 1.30E-04
40 Fe-55 8.40E-07
41 Fe-59 2.20E-07
42 Co-58 3.20E-06
43 Co-60 3.70E-07
44 Sr-89 3.30E-06
45 Sr-90 1.50E-07
46 Sr-91 3.30E-06
47 Sr-92 4.00E-07
48 Y-90 2.70E-08
49 Y-91m 1.80E-06
50
9.56E-02
1.13E-950.00E+002.21E-02
8.04E+00
0.00E+002.40E-116.01E-238.28E-052.70E-98
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
NuclideInitial
Activity (μCi/g)
Decayed Activity (μCi/g)
8.67E-013.65E-022.74E-011.23E-02
7.54E+021.31E+011.10E+04
4.51E+03
1.92E+035.05E+01
2.77E+013.12E+02
9.96E+021.10E-01
1.05E+04
Half Life (Days)
1.00E-01
2.01E-035.73E+095.20E-01
1.10E-02
2.30E-02
4.45E+017.09E+01
6.84E-141.60E-2528.91E-370.00E+000.00E+002.04E-036.13E-041.50E-030.00E+009.95E-011.04E-061.03E-061.03E-868.23E-071.38E-072.39E-063.66E-072.19E-061.50E-07
4.18E-910.00E+000.00E+008.88E-072.22E-183.06E+009.98E-942.53E-09
5.92E-2483.30E-320.00E+000.00E+007.56E+012.27E+015.54E+010.00E+003.68E+043.84E-023.81E-023.83E-823.04E-025.10E-038.83E-021.35E-028.09E-025.54E-03
1.89E-192.60E-018.46E-952.15E-10
5.02E-2492.80E-330.00E+000.00E+00
3.54E-920.00E+000.00E+007.53E-08
3.23E-033.25E-83
6.41E+001.93E+004.70E+000.00E+00
6.86E-034.70E-04
Decayed Activity (Bq/g)
Decayed Activity (MBq)
2.58E-034.33E-047.49E-031.15E-03
3.12E+033.26E-03
4.01E-01
2.67E+003.45E-02
1.13E-011.03E-284.81E-871.11E-11
4.45E-268
3.80E-241.78E-824.10E-07
1.65E-263
3.22E-251.51E-833.48E-08
1.40E-264
×−
21
)2(t
TLn
EDT 009 0808
Page 29 of 31
Doc. Type:
Sequen. Number: 2
Status: S1111 C
Project Number:
0014
Rev.
63000333 000 000
Area : System: Discip. Code:
1
2 Y-91 2.30E-07
3 Y-92 4.90E-07
4 Y-93 1.50E-07
5 Zr-95 2.70E-07
6 Nb-95 2.70E-07
7 Mo-99 3.40E-04
8 Tc-99m 3.20E-04
9 Ru-103 2.30E-07
10 Rh-103m 2.30E-07
11 Rh-106 2.00E-10
12 Ag-110m 6.70E-07
13 Te-127m 1.30E-06
14 Te-127 3.20E-07
15 Te-129m 4.40E-06
16 Te-129 3.80E-06
17 Te-131m 1.00E-05
18 Te-131 2.80E-06
19 Te-132 1.30E-04
20 Te-134 3.20E-06
21 Ba-137m 1.40E-03
22 Ba-140 1.70E-06
23 La-140 6.00E-07
24 Ce-141 2.60E-07
25 Ce-143 2.20E-07
26 Ce-144 1.90E-07
27 Pr-143 2.50E-07
28 Pr-144 1.90E-07
29
30 Table 11: Sludge Isotopic Fingerprint after 30 days
31
32 Notes 1. 1Ci = 37GBq = 3.7E+10Bq
33 2. The Ba-137m value in table 2 above is incorrect, because Ba-137m is actually in secular equilibrium with it's parent,
34 Cs-137, which is long lived in comparison to Ba-137m i.e. 30.1 yrs in comparsion to 2.5mins. This does not
35 affect the conclusions.
36
37 From Ref 6 none of the Isotopes in Table 11 are Alpha emitters
38
39 mass of sludge per year = Density x Volume
40
41 mass of sludge per year = 998.20 x 0.085
42
43 mass of sludge per year = 84.847 kg
44
45 The total activity within the sludge after 30 days decay time is MBq
46
47 The Isotopic fingerprint of the sludge can be found in table 11.
48
49
50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
5.85E+01
4.24E-016.40E+013.50E+01
1.50E-01
2.75E+002.50E-013.93E+01
3.45E-043.90E-02
2.50E+02
4.83E-023.36E+01
1.09E+023.90E-01
1.61E-073.05E-677.68E-291.95E-071.49E-071.77E-072.76E-401.35E-07
4.32E-2390.00E+006.16E-071.07E-062.23E-302.37E-06
5.41E-193
5.96E-031.13E-622.84E-247.22E-035.51E-03
3.97E-028.26E-26
6.54E-031.02E-355.01E-03
1.60E-234
8.77E-022.00E-188
0.00E+002.28E-02
5.06E-049.57E-642.41E-256.13E-044.68E-04
0.00E+001.94E-033.37E-037.01E-277.44E-03
1.70E-189
5.55E-048.68E-374.25E-04
1.36E-235
1.25E+001.74E-023.20E+00
1.77E-03
2.85E+021.36E+011.20E-02
3.00E-02
1.28E+011.68E+003.25E+011.38E+00
5.40E-080.00E+00
3.33E-072.53E-121.37E-076.06E-14
0.00E+001.96E-07
1.77E-07
2.99E-3070.00E+00
5.96E-13
5.07E-032.24E-096.54E-03
7.24E-031.10E-3020.00E+001.23E-029.35E-08
2.21E-080.00E+00
1.87E-090.00E+006.15E-040.00E+000.00E+001.04E-037.93E-09
3.14E+03
4.30E-041.90E-105.54E-04
Total Activity 3.14E+03
1.70E-040.00E+00
2.00E-030.00E+00
EDT 009 0808
Page 30 of 31
Doc. Type:
Sequen. Number: 2
Status: S1111 C
Project Number:
0014
Rev.
63000333 000 000
Area : System: Discip. Code:
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2 The LLWR D1 form (Acceptance in principle) asks specifically for the following istopes:
3
4 Uranium = 0 MBq
5 Ra-226 = 0 MBq
6 Th-232 = 0 MBq
7 Other alpha = 0 MBq
8 C-14 = 0 MBq
9 I-129 = 7.53E-08 MBq
10 H-3 = 3.12E+03 MBq
11 Co-60 = 1.15E-03 MBq
12 Other radionuclides = 1.33E+01 MBq
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50©Aker Solutions E & C Ltd.
The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
EDT 009 0808
Page 31 of 31
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2 References
3 1 EPS-GW-GL-700 Rev 0. Euro DCD, section 11.4.2.1, Pg 11.4-4 and Table 11.4-1.
4 2 EPS-GW-GL-700 Rev 0. Euro DCD, table 11.1-7
5 3 EPS-GW-GL-700 Rev 0. Euro DCD, table 11.1-8 - Realistic source terms
6 4 Perry's Chemical Engineers' Handbook, Seventh Edition. Pg 16-10.
7 5 http://www.defra.gov.uk/environment/radioactivity/waste/pdf/definitions0905.pdf
8 6 http://nucleardata.nuclear.lu.se/NuclearData/toi/index.asp
9 7 EPS-GW-GL-700 Rev 0. Euro DCD, table 11.1-1
10 8 EPS-GW-GL-700 Rev 0. Euro DCD, Page 11.4-13
11 9 T/WPS/320/E/02 - Nirex Waste Package Specification and Guidance Documentation Specification for 3m 3 Drum
12 10 UKP-GW-GL-790. AP1000 Environment report.
13 11 2007 UK Radioactive Waste Inventory. Waste data sheet 3S06 - LLW resins.
14 12 http://www.theconstructioncivil.com/2009/09/density-of-concrete.html
15 13 Conditions for acceptance for disposal of Radioactive Active Waste at the Low Level Waste Respository.Issue 01/08
16 14 Ans standard for waste liquid (ans/ansi 55.6 1993) for liquid and misc. drains.
17 15 EPS-GW-GL-700 Euro DCD rev 0. Table 11.1-8 Realistic Source terms
18 16 2007 UK Radioactive Waste INventory. Waste data sheet 3S07 - Station Maintenance and Operations LLW. .
19 17 UKP-GW-GL-004. Process Mass Balance for AP1000 Solid Waste ((63000333-000-000-111-C-0001))
20 18 Perry's Chemical Engineers' Handbook, Seventh Edition. Pg 2-91.
21 19 EPS-GW-GL-700. Euro DCD, Rev 0. Table 11.1-5
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S1
Doc. Type:
Sequen. Number:
000 000 111 C 0014
Area: System: Discip. Code:Project Number:
63000333
©Aker Solutions E & C Ltd. The information on this sheet may be used only for the purposefor which it is supplied by the Company and must not be shown
to third parties. This sheet and all copies must be returned on demand.
EDT 009 0808